JPN-87-020, Submits plant-specific Info Re Standby Liquid Control Sys, Alternate Rod Insertion Sys & Recirculation Pump Trip Sys to Demonstrate Conformance to ATWS Rule Requirements,Per NRC 870108 Request

Submits plant-specific Info Re Standby Liquid Control Sys, Alternate Rod Insertion Sys & Recirculation Pump Trip Sys to Demonstrate Conformance to ATWS Rule Requirements,Per NRC 870108 Request

ML20215H541
Person / Time
Site:	FitzPatrick
Issue date:	04/15/1987
From:	Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
JPN-87-020, JPN-87-20, NUDOCS 8704200390
Download: ML20215H541 (7)

Text

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123 Main Street WNte Plains, New Wik 10601 914 681.6240 A NeWrkhr aesa c. = -

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& Authority 3py11 13, 1987 JPN-87-020 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.C. 20555

Subject:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 ATWS Rule (10 CFR 50.62): Plant Specific Review

References:

1. NRC Letter, H. Abelson to J. C. Brons, dated January 8, 1987 ([[::JAF-87-009|JAF-87-009]]) regarding ATWS Rule Plant Specific Reviews.

Dear Sir:

Reference 1 requested plant specific information for the Standby Liquid Control (SLC) System, Alternate Rod Insertion (ARI) System, and Recirculation Pump Trip (RPT) System to demonstrate conformance with ATWS Rule requirements.

The following plant specific information is provided:

A. SLCESTEM

1. The SLC system will be designed to supply 50 gpm of enriched i sodium pentaborate solution (26.7 atom percent of B-10) to l the reactor vessel to meet ATWS requirements. This design was presented in the BWR Owners Group licensing topical report (NEDE-31096-P) and accepted by NRC in the staff's Safety Evaluation enclosed with Reference 1. The proposed SLC system design is an NRC approved design meeting ATWS requirements.

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2. Surveillance and positive verification by periodic testing will be performed to assure that the correct isotopic enrichment is maintained. When additional chemicals, e.g.,

boron or boric acid are added to the storage tank, isotopic enrichment of D-10 in the solution will be votified.

Frequency of porlodic testing for isotopic enrichment will be similar to that for solution concentration verification l (once/ month) and will be discussed in the submittal of Technical Specification changes.

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3. The Technical Specifications will be revised to reflect the increased flow and the increased enrichment of B-10 isotope in the sodium pentaborate solution. Also, the volume-concentration curve will be modified to reflect the enriched boron solution. Proposed Technical Specification changes will be submitted 120 days prior to startup from the Reload 8/ Cycle 9 refueling outage.

B. ARI System

1. The Fitzpatrick plant ARI system will be designed in accordance with the guidance provided in the staff's Safety Evaluation of the topical report. The checklist contained in Appendix A of the Safety Evaluation has been completed and is included as Attachment 1. The checklist demonstrates conformance with the ARI design basis requirements and objectives. The requirements for qualification information on isolation devices contained in Appendix B of the Safety Evaluation will also be met.

The ARI system design will utilize five valves as shown in Attachment 2. The ARI system design concept is the same as submitted in the topical report.

The ARI logic will be initiated by sensors that are separate from the RPS sensors. ARI logic will be one out of two taken twice for reactor vessel low water level or reactor vessel high pressure, as shown in Attachment 3.

Page 15 of the Safety Evaluation states that the ARI system should be testable at power using a redundant 2 out of 2 logic arrangement. The testability of the FitzPatrick ARI system at power uses a different logic, i.e., one out of two taken twice, which is the same as the RPS logic. Each individual level and pressure instrument can be tested during plant operation without initiating the ARI system since one level or pressure signal in each of the two channels must be present to complete the actuation signal.

2. No Technical Specification changes will be required for the ARI system.

C. RpT System The Authority intends to endorse the BWR Owners Group position that redundant trip coils for each recirculation pump are not required to comply with the ATWS Rule. A submittal from the Owners Group to NRC regarding this matter is expected in the near future. Pending resolution of this issue, no modifications to the FitzPatrick RPT system are presently planned.

Sh:uld y:u or ysur ctaff have any questions regarding this matter, please contact Mr. J. A. Gray, Jr. of my staff.

Very truly yours,

[ , ofn . Brons

.,' 'enior Vice President uclear Generation Enclosures cc: Office of the Resident Inspector U. S. Nuclear Regulatory Commission P. O. Box 136

( Lycoming, New York 13093 U. S. Nuclear Regulatory Commission

, - Region I

' 631 Park Avenue

! King of Prussia, PA 19406 l-l s

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Attachment 1 to JPN-87-020 APPENDIX A ,

. CHECKLIST FOR PLANT SPECIFIC REVIEW OF J V

ALTERNATE ROD INJECTION SYSTEM (ARI) r Con ormance with ARI SER

1. ARI system function time Rod injection motion will begin within 15 seconds ,

and be completed within 25 seconds from ARI initiation

• Yes j

2. Safety-related requirements (a) Class 1E isolators are used to interface with safety-related systems Yes (b) Class 1E isolators are powered from a Class IE source Yes (c)Isolatorqualificationdocumentsare available for staff audit Yes

3. Redundancy The ARI system performs a function redundant to the backup scram system Yes

4. Diversity from existing RTS (a)ARIsystemisenergize-to-function Yes (b) ARI system uses DC powered valves Yes (c) Instrument channel components (excluding sensors but including all signal conditioning and isolation devices) are diverse from the the existing RTS components. Yes

5. Electrical independence from the existing RTS (a) ARI actuation logic separate from RTS logic (Note 1) y,g (b) ARI circuits are isolated from safety related circuits Yes Note 1: ARI design will use sensors separate from the RTS sensors.

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/ 6. Physical separation from the existing RTS n #;

(a) ARI system is physically separated from RTS Yes

7. Environmental Qualification ARI equipments are qualified to conditions during an ATWS event up to the time the ARI function is completed Yes

8. QualityAssura)ce (a) Comply with Generke Letter 85-06 ye,

9. Safety-related power supply (a) ARI system power independent from RTS y, j

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(b)ARIsystemcanperformitsfunction during any loss-of-offsite power event Yes

}'.10. Testability at Power

< (a) ARI testable at power Yes t (b) Bypass features confom to bypass criteria used in RTS Yes

[ 11. Inadvertent Actuation (a) AR Actuation setpoints will not challenge scram Yes (b) Coincident logic is utilized in ARI design _ Yes

12. Manual Initiaiion (a) Manual initiation capability is provided Yes

13. Infomation Readout (a) Information readout is provided in main control room Yes

• . 14. Completion of protective action once it is initiated _ Yes i

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